ML18101A374

From kanterella
Jump to navigation Jump to search
Safety Evaluation Supporting Licensee 930305 & 940427 Responses to NRC Bulletin 90-001,suppl 1
ML18101A374
Person / Time
Site: Salem, Hope Creek  
Issue date: 12/02/1994
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML18101A373 List:
References
IEB-90-001, IEB-90-1, NUDOCS 9412080250
Download: ML18101A374 (3)


Text

,,---

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION U.S. NUCLEAR REGULATORY COMMISSIONCNRCl BULLETIN 90-01 SUPPLEMENT 1. LOSS OF FILL-OIL IN TRANSMITTERS MANUFACTURED BY ROSEMOUNT PUBLIC SERVICE ELECTRIC & GAS COMPANY OF NEW JERSEY HOPE CREEK NUCLEAR STATION. UNIT 1. SALEM GENERATING STATION. UNITS 1 AND 2 DOCKET NOS. 50-354, 50-272. 50-311

1. INTRODUCTION NRC Bulletin 90-01 Supplement 1, was issued by the NRC on December 22, 1992, to inform addressees of activities taken by the NRC staff and the industry in evaluating Rosemount transmitters and to request licensees to take actions to resolve this issue. The Supplement requests utilities to review the information for applicability to their facilities, perform testing on the transmitter commensurate with its importance to safety and demonstrated failure rate, and modify, as appropriate, their actions and enhanced surveillance programs.

The Supplement also requested that the licensee provide a response that included a statement as to whether or not the licensee will take the actions requested, a list of specific actions that the licensee would complete, and the schedule for completing the actions. Additionally, when the specific actions committed to in the licensee's response were completed, the licensee was required to provide a statement confirming said completion.

If the licensee did not plan to comply with all of the Requested Actions as delineated in the Supplement, a statement was required identifying those Requested Actions not taken, as well as an evaluation which provided the bases for Requested Actions not taken.

2.0 DISCUSSION AND EVALUATION The licensee for the Hope Creek Plant, Unit 1, and Salem Generating Station Plant, Units 1 and 2, Public Service Electric and Gas Company of New Jersey, responded to NRC Bulletin 90-01 Supplement 1, in submittals dated March 5,1993, and April 27, 1994.

The Requested Actions delineated in Supplement 1 asked that licensees review plant records and identify any Rosemount Model 1153 Series B, Model 1153 Series D, and Model 1154 transmitters manufactured before July 11, 1989, that are used (or may be used in the future} in either safety-related systems or systems installed in accordance with 10 CFR 50.62 (the ATWS rule}. Additionally, the licensee was to commit to a specified enhanced surveillance monitoring frequency that corresponded to the normal operating pressure of the transmitters identified.

Furthermore, the licensee was requested to evaluate their enhanced surveillance monitoring program.

9412080250 941202 PDR ADOCK 05000272 f!il PDR

2 A detailed evaluation of the licensee's response is documented in the enclosed contractor's report.

3.0 CONCLUSION

The staff has reviewed the licensee's response to NRC Bulletin 90-01 Supplement I, and concluded that the licensee conforms to the Requested Actions and has completed the reporting requirement~. Compliance with applicable Commission requirements may be the subject of NRC audits or inspections in the future.

Principal Contributor:

D. Spaulding Date: December 2, 1994

~~~I I~~~~~

NATIONAL ENGINEERING LABORATORY Evaluation of Utility Response to Supplement 1 t~ NRC Bulletin 90-01:

Hope Creek and Salem-1/-2

~Lockheed Idaho Technologies Company INEL-94/0168 November 1994 Alan C. Udy Idaho National Engineering Laboratory Work performed und,

DOEComra, No. DE-AC07-94!Dl32: